Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors

Author:

Unal C.,Williams B.,Hemez F.,Atamturktur S.H.,McClure P.

Funder

US Department of Energy

Nuclear Energy Division

Nuclear Energy Advanced Modeling and Simulation Office

Fuels and Verification and Validation Program Elements

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference42 articles.

1. Atamturktur, H.S., et al., 2010. A Forecasting Metric for Predictive Modeling. Los Alamos National Laboratory report, LA-UR-10-03699.

2. Foundations of Complex-System Theories;Auyang,1998

3. Quantifying reactor safety margins: application of CSAU to a LBLOCA. Part 1: an overview of the CSAU evaluation methodology;Boyack;Nucl. Eng. Des.,1990

4. Boyack, B.E., et al., 1994. Quantifying Reactor Safety Margins, Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-of-Coolant Accident. NUREG/CR-5249 EGG-2552, December.

5. Boyack, B.E., et al., 2001. Phenomenon Identification and Ranking Tables (PIRTs) for Rod Ejection Accidents in Pressurized Water Reactor Containing High Burnup Fuel. NUREG/CR-6742, Los Alamos National Laboratory report, LA-UR-99-6810.

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